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Division Spotlight
Fuel Cycle & Waste Management
Devoted to all aspects of the nuclear fuel cycle including waste management, worldwide. Division specific areas of interest and involvement include uranium conversion and enrichment; fuel fabrication, management (in-core and ex-core) and recycle; transportation; safeguards; high-level, low-level and mixed waste management and disposal; public policy and program management; decontamination and decommissioning environmental restoration; and excess weapons materials disposition.
Meeting Spotlight
International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025)
April 27–30, 2025
Denver, CO|The Westin Denver Downtown
Standards Program
The Standards Committee is responsible for the development and maintenance of voluntary consensus standards that address the design, analysis, and operation of components, systems, and facilities related to the application of nuclear science and technology. Find out What’s New, check out the Standards Store, or Get Involved today!
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Latest News
Argonne’s METL gears up to test more sodium fast reactor components
Argonne National Laboratory has successfully swapped out an aging cold trap in the sodium test loop called METL (Mechanisms Engineering Test Loop), the Department of Energy announced April 23. The upgrade is the first of its kind in the United States in more than 30 years, according to the DOE, and will help test components and operations for the sodium-cooled fast reactors being developed now.
Djordje I. Tomašević, Edward W. Larsen
Nuclear Science and Engineering | Volume 122 | Number 3 | March 1996 | Pages 309-325
Technical Paper | doi.org/10.13182/NSE96-A24167
Articles are hosted by Taylor and Francis Online.
The simplified P2 (SP2) approximation to the transport equation is derived by a formal procedure and by a variational analysis. The variational analysis yields the SP2 equations, together with interface and Marshak-like boundary conditions. Numerical calculations show that the resulting SP2 solution is generally more accurate than the P1 solution for both integral quantities and detailed flux distributions, except near material interfaces, where the SP2 solution is discontinuous.
